ML19289F127
| ML19289F127 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 03/29/1978 |
| From: | Leonard J POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| JAFP-78-149, NUDOCS 7906040305 | |
| Download: ML19289F127 (2) | |
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POWER AUTHORITY OF THE STATE OF NEW YORK LAMES A. FtTzPATRICK NUCLEAR POWER PLANT S
JOHN D. LEONARD, JR.
P.o. Box 41 Resident Manager Lycoming, New York 13093 March 29, 1978 31s.342 m JAFP 78-149 Boyce H. Grier, Director inspection & Enforcement Division U.S. Nuclear Regulatory Commission Region I 631 Park Avenue King of Prussia, Pennsylvania 19406 3.d
SUBJECT:
Prompt Reportable Occurrence (Potential)
Regarding Nuclear Boiler Safety Relief Valve Pioing
Dear. Mr. Grier:
On January 5,1978, it was reported to your staff that during a review of the nuclear boiler safety relief valve piping, it was determined that the inlet piping to the safety relief valves was 6" double extra strong and that the inside diameter of the installed piping is thus slightly smaller than the inlet piping.
It was further stated that we had conducted a preliminary evaluation of the effects of using pipe of this diameter and that although we did not consider this to have significant impact on plant relief valve capacity, we were requesting the nuclear steam supply vendor to perform a detailed examina-tion of the effect of the decreased inlet pipe diameter. We received, on the 27th of March 1978, the General Electric analysis and safety review which we had requested.
The results of this analysis concludes that the installed scheduled extra strong safety relief valve inlet piping does not compromise the continued safe operation of the James A. FitzPatrick Nuclear Power Plant during cycle 1I and confirms our analytical estimate of the 1imiting peak pressure increase which we reported to you in our transmittal of January 5,1978.
In addition, during the period that General Electric was conducting this an'alysis, the plant staff researched the startup test data available at the site.
It has been determined that General Electric utilized extremely conservative parameters in their analysis.
The actual measured capacity of the 2236 079 0
b 7 906040 K 8
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Boyce H. Grier, Director March 29, 1978 inspection & Enforcement Division JAFP 78-149 U.S. Nuclear Regulatory Commission Page
SUBJECT:
Prompt Reportable Occurrence (Potential)
Regarding Nuclear Boller Safety Relief Valve Piping safety relief valves is significantly greater than the nominal capacity required.
In fact, frcm the empirical data at the plant site, an excess of approximately 140,000 pounds per hour over the nominal capacity of 830,000 pounds per hour per valve was demonstrated with the presently installed piping.
The General Electric analysis and the start up test data supporting these facts, are available at the plant for review by your staff if so desired.
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Very trulyg ours,
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s RESIDENT MANAGER G. T. Berry, General Manager & Chief Engineer ( )
Distribution:
P. W. Lyon, Manager - huclear Operations A. Klausmann, Director, quality Assurance M. Cosgrove, Site quality Assurance Engineer J. F. Davis, Chairman, Safety Review Committee L. R. Bennett, General Counsel P. J. Early, Assistant Chief Engineer, Projects R. J. Pasternak, Superintendent of Power 2236 080
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